Simulation of Subcooled Boiling in Multiphase CFD Code CFX

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000045" target="_blank" >RIV/46356088:_____/19:N0000045 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Simulation of Subcooled Boiling in Multiphase CFD Code CFX

Popis výsledku v původním jazyce

This paper presents a validation of multiphase Computational Fluid Dynamics (CFD) code Ansys CFX 18 on selected experiments with the subcooled boiling flow. Ansys CFX code can simulate multiphase flow by solving three balance equations for each phase (Euler-Euler approach). Boiling on the heated wall can be simulated with the model proposed by Kurul and Podowski. A set of mathematical models of physical phenomena in boiling bubbly flow was selected and tested on the following experiments with subcooled boiling: DEBORA experiments, ASU experiments, FRIGG FT-6a experiment, and Bartolomej et al. experiment. The DEBORA experiment is a vertical pipe with a heated wall. The working fluid is freon R-12. The ASU boiling experiment is a vertical annular channel with a heated inner wall and freon R-113. The FRIGG FT-6a experiment is a vertical channel with 6 heated rods and boiling water. The Bartolomej experiment is a vertical heated pipe with boiling water. It was found out that CFX code can reasonably reproduce measured data in all these experiments. At the end of this paper, we present an application of this modeling approach to the real case with a complicated geometry: simulation of subcooled boiling in the VVER-1000 fuel assembly with bent rods. Presented at the 29th Symposium of AER on VVER Reactor Physics and Reactor Safety, At Energoland Mochovce, NPP Mochovce, Slovakia.

Název v anglickém jazyce

Simulation of Subcooled Boiling in Multiphase CFD Code CFX

Popis výsledku anglicky

This paper presents a validation of multiphase Computational Fluid Dynamics (CFD) code Ansys CFX 18 on selected experiments with the subcooled boiling flow. Ansys CFX code can simulate multiphase flow by solving three balance equations for each phase (Euler-Euler approach). Boiling on the heated wall can be simulated with the model proposed by Kurul and Podowski. A set of mathematical models of physical phenomena in boiling bubbly flow was selected and tested on the following experiments with subcooled boiling: DEBORA experiments, ASU experiments, FRIGG FT-6a experiment, and Bartolomej et al. experiment. The DEBORA experiment is a vertical pipe with a heated wall. The working fluid is freon R-12. The ASU boiling experiment is a vertical annular channel with a heated inner wall and freon R-113. The FRIGG FT-6a experiment is a vertical channel with 6 heated rods and boiling water. The Bartolomej experiment is a vertical heated pipe with boiling water. It was found out that CFX code can reasonably reproduce measured data in all these experiments. At the end of this paper, we present an application of this modeling approach to the real case with a complicated geometry: simulation of subcooled boiling in the VVER-1000 fuel assembly with bent rods. Presented at the 29th Symposium of AER on VVER Reactor Physics and Reactor Safety, At Energoland Mochovce, NPP Mochovce, Slovakia.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/TH02020360" target="_blank" >TH02020360: Modelování vzniku CHF - krize varu pomocí výpočetních programů typu CFD</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2019

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů